Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."

From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."

Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) or the (111) planes of the aluminum matrix were observed in overaged specimens."

From abstract: "Four plates of uranium that were fabricated by powder metallurgy techniques and clad with 1100 aluminum by hot pressing were irradiated in the Materials Testing Reactor. Increases of about one-half per cent in length and one per cent in thickness were observed after exposure of 1600 megawatt days per ton. The surfaces of the plates remained smooth."

From abstract: "The Standard Pile was first brought to criticality on July 25, 1953. The first two months of operation permitted calibration of the reactor and preparation of it for use as a neutron source in exponential experiments."

From abstract: "A windlass that operates a safety rod for a nuclear reactor was developed to decelerate the rod after it drops under emergency conditions into the reactor. The windlass is designed to convert the kinetic energy of the falling rod as it nears its limit of travel to rotational energy in the windlass. The conversion is accomplished without the aid of an external power source or an auxiliary snubbing mechanism."

From abstract: "Sample holders and monitoring equipment were designed and fabricated for use in the irradiation of experimental shapes of fuel and target materials in the beryllium reflector of the Materials Testing Reactor. The samples were held in aluminum cases designed to replace certain beryllium blocks of the reflector. Sample holders of alternate designs were made to permit irradiation of samples in the reflector at locations where the shape or position of the reflector blocks would not permit the use of the original design."

From abstract: "A composite ultrasonic unit was developed to indicate the size and location of non-bonded areas and the presence of non-transformed regions in flat uranium fuel elements clad with aluminum. A two-dimensional recorder was developed to yield instantaneous, permanent records of the non-bonded areas on electrosensitive paper. Panel lights indicate the presence of non-transformed regions that have not received proper heat treatment. Defects 1/8" in diameter are consistently detected at an inspection rate of approximately 50 sq. in./min."

From summary: "The concentration of plutonium by cation exchange was significantly improved by using a solution of ammonium lactate and sulfamate as the elutriant instead of nitric and sulfamic acids. The new elutriant permitted essentially complete elution of the plutonium and also avoided formation of gases in the resin bed during elution. At 45ºC, 2.8M ammonium lactate plus 0.15M ammonium sulfamate eluted 99.3 per cent of the total plutonium at an average concentration of 43.8 grams per liter. It was found necessary to elute hydrogen and hydroxylammonium ions from the resin beds before elution of plutonium. The hydroxylammonium ions decompose to form gases in the resin bed at the desired temperature for plutonium elution. The hydrogen ions exchange with ammonium ions of the elutriant and decrease the concentration of plutonium in the eluate."

Technical report. From Abstract : "An analytical method was developed for the determination of Np237 in solutions that contain plutonium and fission products. Np (IV) was extracted into tri-n-octylamine. A quantitative recovery of a Np237 standard was obtained with a coefficient of variation of 1.0% (n=10). A coefficient of variation of 3% was obtained for seven analyses of a process sample."

Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."

Technical report. From Abstract : "The separation of neptunium and plutonium by anion exchange in nitrate solutions was studied under a wide variety of experimental conditions. A method of separation was developed that is adaptable to remote operation in the plant. In the method, Np(IV) and Pu(IV) are absorbed on an anion exchange resin from 8M nitrate solution. The column is washed with 8M HNO3 to remove contaminants; then the Pu is removed as Pu(III) by washing the column with HNO3 containing ferrous sulfamate and hydrazine. Finally, the Np is eluted with dilute HNO3."

Technical report. From Abstract : "Optimum conditions were determined for the precipitation of neptunium (IV) peroxide from nitric acid solutions. The results indicate that the precipitation could be applied successfully on a plant scale. ... Two crystalline modifications of the peroxide were prepared; these two crystalline structures were similar to structures previously reported for plutonium peroxide."

Technical report. From Abstract: "An ion exchange process was demonstrated for the recovery of Pu238 from irradiated neptunium oxide. Three cycles of anion exchange proved adequate for the removal of fission products and for the separation of the neptunium and plutonium from each other."

Technical report issued by E. I. du Pont de Nemours & Co. From Abstract: "Information obtained from investigations pertinent to tritium monitoring and protective measures at the Savannah River Plant are given. These findings were used to establish realistic protective techniques and consequently, to insure the safety of workers exposed to this hazard. Topics included are: contamination, permeation of plastics and rubber, instrumentation, and biological and physical aspects."

Technical report. From Abstract : "Spark counters of the wire plate type are rugged and simple, and their sensitivity is directly proportional to the specific ionization of incident particles. Spark counters are insensitive to beta and gamma radiation but readily respond to alpha particles. With a suitable converter, the spark counter can also be employed as a neutron counter. Spark counters thus appear to be very good candidates for the measurement of neutron flux at reactor startup, where the high background of gamma radiation can be troublesome to other types of counters. A spark counter of cylindrical geometry was built and shown to have adequate sensitivity and stability for such duty."

Technical report. From Abstract : "Curium-242 was experimentally identified as a minor product of the irradiation of neptunium-237 in a nuclear reactor." From Introduction : "Determinations of the half-life, alpha energy, and daughter product of the purified curium nuclide were made in this study to confirm the identity as curium-242."

From abstract: "Calculations are made of the magnitude of the radiation bursts that can occur in a mixer-settler and in a large tank containing U235 solution if the concentration gets out of control. Various rates of increase in concentration are studied and various restraints are imposed on the expansion of the systems. The neutron kinetics equations, with five groups of delayed neutrons, and the equations relating the neutron flux to the pressure and volume of the gas formed by fission fragments are combined into a single first-order nonlinear differential matrix equation which is solved numerically on the IBM 650. In a mixer-settler containing 9.7 kg of U235 the magnitude of the burst was calculated to be about 10^17 fissions, both for low rates of increase in reactivity (<[or equal to]0.01% per sec) regardless of the confinement, and for an unconfined system regardless of the rate of increase reactivity. In a tank containing 88.9 kg of U235 successive bursts of about 10^19 fissions were calculated to occur about 0.5 second apart when the rate of increase in reactivity was about 0.1% per second."

From abstract: "The circumstances are described pertaining to an explosion in a TNX evaporator during the concentration of a uranyl nitrate-nitric acid solution. TBP and Amsco diluent were probably present in the evaporator charge. A laboratory program involving small-scale atmospheric and closed-vessel distillations of various mixtures of UNH, HNO3, Amsco, TBP, and water indicate that an exothermic reaction between TBP and UNH, or between TBP and HNO3, or both, was responsible for the explosion. The danger areas of temperature, TBP concentration, pressure, and heating rate are defined and recommendations are made for safe evaporator operation.

From abstract: "A pump-mix mixer-settler was demonstrated to have an overall efficiency greater than 90 per cent for the extraction of uranyl nitrate from tributyl phosphate at total flow rates up to 45 gallons per minute. Phase separation was satisfactory at 45 gallons per minute, at which flow rate the residence time in the settlers was 1-1/2 minutes. It appeared possible that a throughput approaching 60 gallons per minute would be operable although at an over-all efficiency of less than 90 per cent. The tests were made on a three-stage unit, but the data can be extrapolated to multistage units. The effects of design of the impeller and mixing section, impeller speed, flow rates and ratios, and operating temperatures were studied. The mechanical performance and dependability of the unit were excellent."

From abstract: "An ionization chamber of the integrating type was built that could detect a tritium leak rate of 10[^-13] cc per second within a few minutes, after a gas-collecting period of 16 hours. Electronic circuitry was avoided by using a quartz fiber voltmeter to indicate the rate of discharge of the chamber."

Technical report. From Abstract : "A facility for separation of Pu238 and Np237 from irradiated neptunium dioxide target slugs was designed, constructed, and operated at the Savannah River Laboratory. This report describes the facility and includes design details of equipment." From Summary : "The main problems encountered during the design of the facility were: (1) to provide adequate containment and shielding of the radioactive materials, (2) to select chemical- and radiator-resistant materials, and (3) to provide for remote operation and maintenance of process equipment. ... This report contains a discussion of the major design problems and a detailed description of the facility and equipment."

Technical report. From Abstract: "The thermal conductivities of aluminum-lithium alloys containing up to * wt % lithium were determined at temperatures between 125 and 260ºC. The addition of lithium to aluminum sharply reduces the conductivity from 0.60 cal/(sec)(ºC)(cm) for pure aluminum to 0.22 cal/(sec)(ºC)(cm) for 2 wt % alloys; further addition linearly and more gradually decreases the conductivity to 0.16 cal/(sec)(ºC)(cm) for a 7.9 wt % alloy."

Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."